ENTRY            20508   20070409                             21842050800000001 
SUBENT        20508001   20070409                             21842050800100001 
BIB                 14         29                                 2050800100002 
INSTITUTE  (2GERJUL)                                              2050800100003 
REFERENCE  (J,AKE,20,(4),309,197201)                              2050800100004 
           ((R,JUEL-834,197203)=(T,BLOSER,197202)) Juel-834-rg,   2050800100005 
            197303 - Kernforschungsanlage Juelich report.         2050800100006 
AUTHOR     (M.Bloser)                                             2050800100007 
TITLE      -Absolute measurement of the be-9(N,2N) cross section  2050800100008 
            in the energy region of 2.37 to 3.24 MeV.- (In german)2050800100009 
FACILITY   (CCW  )    Neutron generator, type sames T (400KV,2ma) 2050800100010 
INC-SOURCE (D-D  )    Deuteron-deuterium.                         2050800100011 
INC-SPECT   Quasi-monoenergetic neutrons of 2.37, 2.53, 2.77, 2.992050800100012 
            3.21 and 3.34 MeV energy.                             2050800100013 
SAMPLE     .Be cylinder with 3 cm length, diameter of 5 cm.       2050800100014 
METHOD     .4 pi detection for N,2N.                              2050800100015 
DETECTOR   (STANK)    Gadolinium loaded liquid scintillator (Ne3142050800100016 
            ,0.5 perc. Gd), in tank(60 cm height and diameter)with2050800100017 
            12 inch photo-multiplier (emi 9545B).                 2050800100018 
            Calibrated by Cf-252.                                 2050800100019 
           .He-3 semiconductor spectrometer for neutron monitor.  2050800100020 
MONITOR     Absolute measurement.                                 2050800100021 
           .Incoming neutron intensity was measured by scattering 2050800100022 
            block method using graphite cylinder.  It was not     2050800100023 
            based on the knowledge of other cross-sections.       2050800100024 
CORRECTION  Corrected for energy distribution of incoming neutron 2050800100025 
            and multiple scattering processes in the be target.   2050800100026 
ERR-ANALYS  Relative error. See further detail in text.           2050800100027 
HISTORY    (19730213C)                                            2050800100028 
           (19760420A) Reference changed.                         2050800100029 
           (19760421E)                                            2050800100030 
           (20070314A) Date is corrected                          2050800100031 
ENDBIB              29          0                                 2050800100032 
NOCOMMON             0          0                                 2050800100033 
ENDSUBENT           32          0                                 2050800199999 
SUBENT        20508002   20070409                             21842050800200001 
BIB                  3          3                                 2050800200002 
REACTION   (4-BE-9(N,2N+A)2-HE-4,,SIG)                            2050800200003 
PART-DET   (N    )    Neutrons.                                   2050800200004 
HISTORY    (20070314A)   Reaction code corrected                  2050800200005 
ENDBIB               3          0                                 2050800200006 
NOCOMMON             0          0                                 2050800200007 
DATA                 3          6                                 2050800200008 
EN         DATA       DATA-ERR                                    2050800200009 
MEV        B          PER-CENT                                    2050800200010 
 2.3700E+00 1.5900E-01 9.0000E+00                                 2050800200011 
 2.5400E+00 2.8500E-01 1.2000E+01                                 2050800200012 
 2.7700E+00 3.7900E-01 1.1000E+01                                 2050800200013 
 2.9900E+00 3.8600E-01 1.3000E+01                                 2050800200014 
 3.2100E+00 4.0500E-01 9.0000E+00                                 2050800200015 
 3.3400E+00 4.2500E-01 9.0000E+00                                 2050800200016 
ENDDATA              8          0                                 2050800200017 
ENDSUBENT           16          0                                 2050800299999 
ENDENTRY             2          0                                 2050899999999